This report describes a study performed by the Lawrence Livermore National Laboratory to evaluate the level of safety provided under severe accident conditions during the shipment of spent fuel from nuclear power reactors. The evaluation is performed using data from real accident histories and using representative truck and rail cask ...

The prescription of the initial conditions and the final conditions for a thermal accident for Type B packages are different for differing regulations. This paper presents an analytical method for estimating the effect of the boundary conditions on post-f...

The release and transport of activated materials-of-construction in a fusion reactor during an accident scenario involving overheating and ingress of oxidants is an important area of safety research. This investigation quantified material release characte...

This paper presents a brief summary of condition monitoring results from an NRC-sponsored test program on aging, condition monitoring, and accident testing of Class 1E cables. In addition, since the program has been completed and the final reports have be...

The availability of traveler information regarding accidents, construction activities, road-weather conditions, and flooding events is limited in this study region. The concept underlying this evaluation is that with better road condition information, com...

analytical process, baseline assumptions and final results. .... Specific LWRHU- threatening conditions associated with each environment ... Lockheed Martin ( 1997) Titan IV/Cassini RTG Safety Databook Probability Analysis Final Report, ...

In the past, the selection of representative accidents for refined analysis from the numerous scenarios identified in hazards analyses (HAs) has involved significant judgment and has been difficult to defend. As part of upgrading the Final Safety Analysis Report (FSAR) for the TA-55 plutonium facility at the Los Alamos National Laboratory, an ...

A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the reactor coolant and ...

The prescription of the initial conditions and the final conditions for a thermal accident for Type B packages are different for differing regulations. This paper presents an analytical method for estimating the effect of the boundary conditions on post-fire peak internal package temperatures. ...

... § 71.73 Hypothetical accident conditions. (a) Test procedures...Evaluation for hypothetical accident conditions is to be based... Tests for hypothetical accident conditions must be conducted...been assumed for criticality analysis, immersion under a head...

The containment building surrounding a nuclear reactor offers the last barrier to the release of radioactive materials from a severe accident into the environment. The loading environment of the containment under severe accident conditions may include much greater than design pressures and temperatures. Investigations into the ...

This section of the Accident Model Document (AMD) presents the appendices which describe the various analyses that have been conducted for use in the Galileo Final Safety Analysis Report II, Volume II. Included in these appendices are the approaches, techniques, conditions and assumptions used in the development of the analytical ...

This report presents the work performed to verify the CEFLASH digital computer code modeling of the hydro-dynamic loads in a steam generator tube during a loss-of-coolant accident (LOCA). The test loop simulated the primary side thermal-hydraulic conditio...

The purpose of this task was to investigate on a laboratory-scale the interactions of molten aluminum with stainless steel under hypothetical severe reactor accident conditions. This experimental effort provided data necessary to assess the susceptibility of the reactor vessel to breaching (general through-wall failure of vessel) in ...

...2010-10-01 false Reporting accidents. 195.50 Section 195.50...HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.50 Reporting accidents. An accident report is...

The final report summarizes the results of various research areas concerned with possible disposal-site accidents involving the destruction of containers containing radioactive waste by salt brine. The physico-chemical data obtained are intended to serve ...

This standard aims to satisfy the radiation protection and safety conditions required by Brazilian Nuclear Energy Commission (CNEN) for final disposal of radioactive wastes stored in Abadia de Goias. These wastes are products of the accident happened in 1...

... from 1976 to 1981, examined the relationship between aviation accidents and static ... between certain visual conditions and aircraft accidents (19,20 ...

Appendix B.In-Flight Loss of Control Accidents in Part 121 and Scheduled ... The causal factors of accidents from the National Transportation Safety Board ...

... Title : Accident Data Systems Study Requirements Analysis for an FAA Accident Data System. Descriptive Note : Final rept. Oct 77-Jul 79,. ...

A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the ...

A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the ...

... Accession Number : ADA143667. Title : Accident Management Orientation Guide. Descriptive Note : Final rept.,. Corporate ...

This section of the Accident Model Document (AMD) presents the appendices which describe the various analyses that have been conducted for use in the Galileo Final Safety Analysis Report 2, Volume 2. Included in these appendices are the approaches, techniques, conditions and assumptions used in the development of the analytical models ...

We have reported our findings of the pre-existing leakage areas from the subatmospheric, atmospheric (dry and ice-condenser) PWRs and the BWRs. The subatmospheric plants employ rather tight containment and hence the pre-existing leakage areas are generally quite small (perhaps inconsequential in the progression of severe accidents). The pre-existing leakage areas for other ...

An alternate to the THRESHOLD model used in most severe accident risk assessments has been investigated. One reference plant for each of six containment types has been studied to determine the magnitude of containment leakage that would result from the pressures and temperatures associated with severe accident conditions. Containment ...

Currently no final repository for any type of radioactive waste is operated in Germany. Preliminary Final Storage Acceptance Requirements for radioactive waste packages were published in 1995. Up to now these are the basis for treatment of radioactive waste in Germany. After licensing of the final repository these preliminary waste ...

Although skin contamination by radionuclides is the most common cause of nuclear workers accidents, few studies dealing with the penetration of radioactive contamination through the skin are available. This work is a review of experimental methods that allow to assess transfer of radionuclides through the skin in occupational conditions, with or without ...

The Hazard Analysis consists of a systematic hazard identification and qualitative analysis of the collector subsystem and components in all operational modes and anticipated natural environments. The analysis identifies design criteria and operational constraints to eliminate or control accident potentials caused by human error, environment, deficiency/inadequacy of design, ...

The damage progression of the reactor core and the slumping mechanism of molten material to the lower head of the reactor vessel were examined through simulation of severe accident scenarios that lead to large-scale core damage. The calculations were carried out on a Three Mile Island Unit 2 configuration using the computer code SCDAP/RELAP5/MOD3.2.Different ...

...fissile materials packagings to withstand accident conditions in transportation. 173...fissile materials packagings to withstand accident conditions in transportation. Each...CFR part 71 for ability to withstand accident conditions in...

A description of the Hallam Nuclear Power Facility is presented. The potential hazards and controlling safeguards are discussed. The reactor system, sodium heat transfer system, instrumentation and control, auxiliary systems, fuel and component handling facilities, reactor plant building and facilities, radioactive waste facility, and site are described. Normal ...

Analysis is made of many postulated accidents within the NS Savannah power plant. The accidents include reactivity accidents, mechanical accidents, and miscellaneous accidents. It is concluded that there is no appreciable hazard to the public or the crew even in the event of the maximum ...

This document provides the technical basis for the frequency of a tank bump and for the radiological and toxicological consequences of a tank boiling accident and associated hazardous conditions.

The main phenomena leading to hydrogen generation in the containment of a PWR in accident conditions are described in this report. They are the following: water radiolysis, zirconium cladding oxidation and oxidation of the aluminium of internal structures...

An analysis of the frequency of four different types of rotorcraft accidents was conducted to determine if the number of fatalities and injuries between accident conditions was different. Accidents involving rollover, no rollover, fire, and no fire were s...

...false Telephonic notice of certain accidents. 195.52 Section 195.52 ...HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting...52 Telephonic notice of certain accidents. (a) At the earliest...

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Steam Intrusion from Interfacing Systems. The calculations needed to quantify the risk associated with this accident scenario are included within.

Throughout the Football World Cup Finals of France 1998, patients attended our inner city Accident and Emergency department with a variety of conditions related to the event. Analysis was made on the total of 151 patients who attended with World Cup related presentations during this five-week period. The majority were young men ...

Reintegration into a social and work environment, as the final objective rehabilitation therapy, is one of the greatest challenges faced in this speciality. The aim of this study was to analyse the reintegration into the workforce of 43 upperlimb amputees in Asturias, Spain (1,100,000 inhabitants) whose amputations were as a result of accidents at work. ...

The purpose of this document is to record and evaluate the hazardous conditions associated with remote pit refurbishment using the Pit Viper. These hazardous conditions were identified during a Hazard and Operability Analysis (HAZOP). Included in the evaluation is a comparison to the hazardous conditions currently included in the ...

Technical Basis Document for the Nuclear Criticality Representative Accident and Associate Represented Hazardous Conditions. Revision 2 of RPP-12371 provides accident consequence estimates for a hypothetical criticality event in an above grade facility (e...

A generic spent-fuel storage cask of nodular cast iron with a maximum loaded weight of 102 tons, 88-inch cavity diameter, 14-inch wall thickness and stainless steel heads was used as the basis to conduct structural analysis under regulatory specified accident conditions for transport casks. Several different flaw locations and cask orientations were ...

In a nuclear reactor, the containment represents the final barrier to fission product release following a severe accident. The timing and manner of containment loading are important in determining if a failure occurs and the magnitude of radioactivity release. A variety of computer models have been developed to analyze severe accidents ...

The attached Hazard Analysis consists of a systematic hazard identification and qualitative analysis of the collector subsystem and components in all operational modes and anticipated natural environments. The analysis identified design criteria and operational constraints to eliminate or control accident potentials caused by human error, environment, deficiency/inadequacy of ...

Each year, accidents involving mountain sports have many repercussions, including alarming public opinion and society. This study outlines the results of a qualitative study on the responses of 135 survivors of accidents that took place while mountaineering, climbing, downhill skiing and ski mountaineering, hiking, cross-country biking, and mountain ...

This document describes a major advance in the technology for calculating source terms from postulated accidents at US light-water reactors. The improved technology consists of (1) an extensive data base from severe accident research programs initiated following the TMI accident, (2) a set of coupled and integrated computer codes (the ...

This report documents the final results of the XR2-1 boiling water reactor (BWR) metallic melt relocation experiment, conducted at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission. The objective of this experiment was to investigate the material relocation processes and relocation pathways in a dry BWR core following a severe nuclear reactor ...

An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents ...

From 1975 to present, it has been found that the primary risk to the public health and safety from nuclear power reactors lies in ``beyond design basis'' accidents. During such severe accidents, melting of the reactor core may lead to a loss of primary system integrity, or even containment failure, which will allow escape of significant amounts of ...

This work, the first by native Ukrainian scientists and specialists, views the Chernobyl nuclear accident from the perspective of risk assessment. It describes the accident, the shelter constructed to contain the destroyed reactor, the sites used for disposal and storage of radioactive waste, the environmental contamination, and the effects of the ...

Accident management is examined from several different perspectives. The emphasis is on the role of the operating crew and the technical support provided to them before, during, and after an accident. The relationship among accident management, risk management, and emergency management is examined. The roles played by industry, ...

... National Park Factors that can contribute to visitor accidents Not relevant ...

... The identification of the true causes of hazardous failures and accidents of technical equipment is the necessary condition for developing and ...